辅助加热下HL-2A边界层等离子体数值模拟

以二维边界等离子体流体模拟代码B2.5为核心,编制适合于具有封闭偏滤器位形特征托卡马克的边界层网格划分代码和计算后处理代码.模拟分析HL-2A托卡马克有约3MW辅助加热功率时的边界等离子体特性.结果表明,偏滤器靶板前形成了致密低温等离子体,偏滤器运行于高再循环状态.     

HL-2A装置偏滤器室中性气体压强的初步研究

HL-2A装置上首次实现了偏滤器位形放电。采用专门研制的可在强磁场和强噪声环境下工作的快响应真空电离规对偏滤器室内的中性气体压强进行了测量,给出了HL-2A装置偏滤器有关结构的基础数据。初步研究了偏滤器位形和孔栏位形放电期间偏滤器室中性气体压强的特性。     

HL—1装置边缘分子过程对中性粒子输运的影响

本文采用新版的一维中性粒子输运程序,在平板几何下模拟了HL-1装置边缘8cm区域的分子过程及中性粒子与壁相互作用对中性粒子输运的影响,得到了电离速率的径向分布、稳态中性氢原子径向分布、壁与边缘等离子体区之间、芯部等离子体与边缘等离子体之间中性氢各种粒子通量、能量通量并与只含原子过程的类似计算进行了比较,结果表明边缘区的分子过程对巾性氢原子输运有显著的影响。有些结果得到实验的证实。     

偏滤器靶板附近氦输运的蒙特卡洛模拟

本文用Monte Carlo方法模拟了偏滤器扁平抽气收集板附近区域的氦原子输运。考虑了氦原子被电子碰撞电离,氦原子与等离子体离子之间的弹性散射等原子过程以及离子的热运动和沿磁力线的流动。计算表明当偏滤器等离子体密度在7cm距离内从里向靶板逐渐增加约4.7倍,而温度分布保持不变时,氦灰返回靶板的几率比密度在7cm内向靶板递减4.7倍的通常正分布提高约45％。磁力线与靶板的交角、靶板的温度,边缘等离子体鞘层电位以及不同的靶材料对氦返回靶板几率的影响作了比较。得到的结果对托卡马克聚变裂变增殖堆孔栏和偏滤器工程设计有参考价值。     

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对HL-2A装置限制器位形和偏滤器位形下放电气体分别为氘和氦时的等离子体热辐射测量结果做了初步分析,分析结果表明：在偏滤器室注入惰性气体能够有效的降低到达靶板的热辐射;超声分子束注入时,观测到注入粒子在等离子体中输运过程;氦放电时的辐射比值明显高于氘放电时的比值;真空室器壁的处理能够有效地降低辐射损失,硅化对器壁条件的改善效果明显。     

Monte Carlo Simulation of Helium Transport in the Vicinity of Divertor Plate

A Monte Carlo code “1DHET” has been utilized for simulating the transport of neutral helium near divertor flat pumping target plate. The dominant atomic processes of electron impact ionization and elastic scattering by plasma ions are included. The thermal and streaming motion of the ions along the magnetic field is taken into consideration. Calculations show that the probability of neutral helium turning back to the target plate will increase by 45% if the divertor edge plasma density is smoothly raised up to 4.7 times higher at the divertor plate than that at 7cm apart inward as compared with the ordinary outward decreasing density profile while keeping temperature profile fixed. The temperature decreases smoothly from 40 eV at z = 7 cm to 3 eV at the plate. The effects of angle between the magnetic field and the target plate, the temperature of plate, edge plasma sheath potential and different target materials on the probability of helium particles scattered back to the plate are studied.     

The first results of divertor discharge and supersonic molecular beam injection on the HL-2A tokamak

HL-2A tokamak is the first tokamak with divertors in China. The plasma boundary and the position of the striking point on the target plates of the HL-2A closed divertor were simulated by the current filament code and they were in agreement with the diagnostic results in the divertor. Supersonic molecular beam injection (SMBI) system was first installed and tested on the HL-2A tokamak in 2004. In the present experiment low pressure SMBI fuelling on the HL-2A closed divertor was carried out. The experimental results indicate that the divertor was operated in the `linear regime' and during the period of SMB pulse injection into the HL-2A plasma the power density convected at the target plate surfaces was 0.4 times of that before or after the beam injection. It is a useful fuelling method for decreasing the heat load on the neutralizer plates of the divertor.     

HL-2M装置雪花减偏滤器热疲劳分析

利用SOLPS软件,采用有限元数值计算方法,模拟计算了HL-2M装置雪花减偏滤器靶板上热负载分布,分析了偏滤器温度及热应力分布,并使用ITER内部器件设计评判标准对HL-2M偏滤器结构进行热疲劳寿命的评估。结果表明,在低周循环下靶板大部分区域不会经历严重的塑性疲劳,但距离外侧抽气口4mm位置拱顶区域循环寿命约为1963次。模拟结果对HL-2M装置偏滤器设计具有一定参考意义。     

HL-2M装置常规偏滤器与雪花减偏滤器热工水力分析对比

采用SOLPS程序模拟预测HL-2M装置常规和雪花减偏滤器靶板上的热通量。当流入边缘等离子体区域的热功率约为10MW时,利用CFX/ANSYS软件分析这两类偏滤器各结构、冷却水温度分布及形变和热应力分布情况。结果表明:等离子体总功率相同,雪花减偏滤器靶板上的最高温度比常规偏滤器低169℃;雪花减偏滤器结构所承受的最大热应力和形变比常规偏滤器低约3/7。不改变热负载剖面分布,按一定比例提升热流密度或延长放电时间,雪花减偏滤器体现出比常规偏滤器靶板温升低、冷却水温均衡等优点。因此,雪花减偏滤器能处理更多流进偏滤器区域的热能,有效地降低偏滤器工程设计要求。     

HL-2A装置送气和加料的脱靶特性

HL-2A装置辐射偏滤器实验采用边缘补充送气和分子束加料等方法来提高主等离子体密度,降低边缘等离子体温度、增加辐射功率分额,获得脱靶等离子体。偏滤器室内进行主动补充送气或者注入惰性气体杂质,降低偏滤器等离子体温度,获得脱靶等离子体,并首次获得了超声分子束注入产生脱靶等离子体的实验结果。利用HL-2A装置偏滤器同一极向截面内外中性化板上安装的嵌入式探针阵列和偏滤器室安装的电动探针系统,测量了偏滤器靶板上和偏滤器室的等离子体参数及其分布,并进行了相关分析和改善约束以及偏滤器脱靶等离子体运行模式下等离子体行为的研究。     

HL-2A装置偏滤器的脱靶等离子体实验

在HL-2A装置偏滤器靶板上采用嵌入式静电三探针阵列和偏滤器室内的电动扫描四探针组测量了同一极向截面的内外中性化板上和偏滤器室内的电子温度、密度、悬浮电位、空间电位、电场、电子压强及其分布,研究了偏滤器中等离子体参数的分布及非对称性和脱靶等离子体运行模式下的等离子体行为,开展了偏滤器脱离靶板等离子体的实验研究。利用主真空室的快速往复扫描三台阶式六探针系统测量了主等离子体边缘和偏滤器室内的等离子体温度、密度、粒子通量和中性粒子密度等参数,研究了脱靶等离子体的形成过程、物理特性、控制方法,以及对主等离子体性能的影响。     

HL-2A装置大拉长比和三角形变等离子体位形设计

介绍了基于MATLAB 程序自主开发的等离子体位形编辑和设计代码SE,包括其设计原理、主要功能、人机界面和操作步骤。通过SWEQU 代码对SE代码的准确性进行了有效验证,分别用上述两种代码设计和验证了两种具有中等拉长比和三角形变位形的放电参数。具有较高拉长比和三角形变位形的实现需要投入装置的上偏滤器线圈来突破圆形截面的限制。最后通过SE代码编辑了一个较大拉长比和三角形变的等离子体位形,并获得了相应的放电参数。结果表明,在HL-2A 装置投入上偏滤器线圈后,可以得到具有较大拉长比和三角形变的新等离子体位形,这些位形为提高HL-2A 等离子体的品质奠定了坚实的基础。     

Analyses of edge plasma characteristics in HL-2A

The edge plasma characteristics are studied by both a movable array of Mach/Reynolds stress/Langmuir 10-probes in the boundary region and the fixed flush probe arrays on the 4 divertor neutralization plates at the same toroidal cross-section in the HL-2A tokamak. The dependence of the Reynolds stress on poloidal flow in the edge plasma is analysed. The result indicates that the sheared poloidal flow in tokamak plasma can be induced by the radial gradient of Reynolds stress. In the divertor experiments of HL-2A, the profiles of the electron temperature, density and floating potential on divertor plates are measured by the flush probe arrays. The edge electron temperature in divertor configuration is higher than that in limiter configuration. The temperature asymmetry between outer and inner target plates is observed. The result of magnetic surface reconstructed from 18 Mirnov coils signals is presented. Both the particle recycling and the impurity flux in the bulk plasma during divertor discharges are discussed. Neutral gas pressure in divertor chamber, measured by fast ionization gauge during divertor discharge, is given.     

Neutral transport code for rovibrational population calculation of molecular hydrogen in large helical device plasmas

An rovibrationally resolved collisional-radiative model of molecular hydrogen (K. Sawada and M. Goto, Atoms 4: 29, 2016) is included in the authors' neutral transport code for large helical device (LHD) plasmas. The spatial distributions of the electron temperature and density, including the divertor and divertor leg regions, are given to the code. The molecules released from the graphite divertor target are tracked. The initial rotational and vibrational states of the released molecules are provided by simulation using a molecular dynamics model. The rovibrational population produced in an LHD plasma is evaluated.     

HL-2A偏压偏滤器物理设计

根据已有的理论模型,推算出了HL-2A偏压偏滤器的理论电流为1．5kA、偏压电压为200V,并对HL-2A偏压偏滤器做出了初步设计。HL-2A装置采用偏压后,有可能降低L-H模转变阈功率,增加偏滤器等离子体密度、压强和滞留时间,改善约束,改善内外靶板功率沉积的非对称性,提高排灰效率及提高偏滤器性能。     

托卡马克边界等离子体数值模拟

本文用数值模拟法，通过数值求解二维多流体等离子体输运方程。来模拟托卡马克边界等离子体输运过程和输运特性。模拟计算的结果，对托卡马克偏滤器和第一壁的设计有重要意义。     

HL-2A 装置偏滤器改造的初步设计

根据HL- 2A 装置的结构特点, 提出了HL- 2A 装置偏滤器系统改造的基本方向。对HL- 2A 极向场线圈系统进行了优化设计, 计算了单零平衡位形, 进行了开放式偏滤器的结构设计, 并对新的偏滤器系统进行了热分析和结构分析。结果表明, 新的偏滤器系统新的偏滤器系统能够满足具有一定拉长比和三角形变的等离子体放电要求。     

Implementation of a separate fluid-neutral energy equation in SOLPS-ITER and its impact on the validity range of advanced fluid-neutral models

In plasma edge transport codes for nuclear fusion devices, fluid-neutral models offer an interesting alternative to the currently used kinetic Monte Carlo simulations, especially for cases of high ion-neutral collisionality. In this paper, we elaborate a separate neutral energy equation in the state-of-the-art SOLPS-ITER code suite, which previously assumed perfect ion-neutral temperature equilibration. Furthermore, we study the coupled plasma-neutral solutions for a range of divertor operating regimes, proving the validity of these fluid-neutral models for high-recycling and detached regimes.     

Hybrid Method for Tokamak MHD Equilibrium Configuration Reconstruction

A hybrid method for tokamak MHD equilibrium configuration reconstruction is proposed and employed in the modified EFIT code. This method uses the free boundary tokamak equilibrium configuration reconstruction algorithm with one boundary point fixed. The results show that the position of the fixed point has explicit effects on the reconstructed divertor configurations. In particular, the separatrix of the reconstructed divertor configuration precisely passes the required position when the hybrid method is used in the reconstruction. The profiles of plasma parameters such as pressure and safety factor for reconstructed HL-2A tokamak configurations with the hybrid and the free boundary methods are compared. The possibility for applications of the method to swing the separatrix strike point on the divertor target plate is discussed.